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Treatment method and system for waste liquid produced by high temperature gas-cooled reactor fuel elements

A high-temperature gas-cooled reactor and fuel element technology, which is used in radioactive purification, nuclear engineering and other directions to achieve significant environmental and economic benefits, and to achieve the effects of resource recycling and waste volume reduction.

Active Publication Date: 2021-12-14
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0009] A main purpose of the present disclosure is to overcome at least one defect of the above-mentioned prior art, and provide a treatment method and system for waste liquid produced by high-temperature gas-cooled reactor components. Since the method does not need to add other chemicals, it will not cause secondary problems. Secondary pollution problems, and most of the useful substances in the waste liquid can be recycled, realizing the recycling of resources, with significant environmental and economic benefits

Method used

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  • Treatment method and system for waste liquid produced by high temperature gas-cooled reactor fuel elements
  • Treatment method and system for waste liquid produced by high temperature gas-cooled reactor fuel elements
  • Treatment method and system for waste liquid produced by high temperature gas-cooled reactor fuel elements

Examples

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Effect test

Embodiment 1

[0064] This example is used to illustrate the use of figure 1 The device shown is the treatment of waste liquid produced by high temperature gas-cooled reactor fuel elements.

[0065] The waste liquid to be treated is the aging liquid of the high temperature gas-cooled reactor core preparation process, and the evaporation area is 0.3m 2 A scraper-type thin-film evaporator (the material of the evaporation barrel is high borosilicate glass) is used to treat the waste liquid. The process parameters of the evaporation process are as follows:

[0066] Evaporator inner wall temperature: 90°C, scraper speed: 150r / min; circulating cooling water temperature: 5°C-10°C, feed rate: 10L / h, vacuum in the system: -0.08MPa, processing time: 10 hours, Use 20L of water to absorb the tail ammonia gas. 60L of condensate and 35L of raffinate were obtained respectively, and the composition of feed liquid before and after treatment is shown in Table 1.

[0067]

[0068] The resulting raffinat...

Embodiment 2

[0072] The method of Example 1 was used to treat the high temperature gas-cooled reactor fuel element production waste liquid. The difference is to change the process parameters of the evaporation process:

[0073] Evaporator inner wall temperature: 70°C; scraper speed: 200r / min; circulating cooling water temperature: 5°C-10°C; feed rate: 10L / h; vacuum degree in the system: -0.09MPa; processing time: 10 hours, Use 20L of water to absorb the tail ammonia gas. 50L of condensate and 45L of raffinate were obtained respectively, and the composition of feed liquid before and after treatment is shown in Table 2.

[0074] Table 2

[0075]

Embodiment 3

[0077] The method of Example 1 was used to treat the high temperature gas-cooled reactor fuel element production waste liquid. The difference is that the waste liquid to be treated is the washing liquid of the high temperature gas-cooled reactor core preparation process. The evaporation area is 0.3m 2 The scraper type thin film evaporator (the material of the evaporating barrel is high borosilicate glass) is used to treat the waste liquid. Process parameters are as follows:

[0078] Evaporator inner wall temperature: 90°C; scraper speed: 200r / min; circulating cooling water temperature: 5°C-10°C; feed rate: 10L / h; vacuum degree in the system: -0.09MPa; processing time: 10 hours, Use 20L of water to absorb the tail ammonia gas. 75L condensate and 25L raffinate were obtained respectively, and the composition of feed liquid before and after treatment is shown in Table 3.

[0079] table 3

[0080]

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Abstract

The disclosure provides a method and system for processing waste liquid produced by high-temperature gas-cooled reactor fuel elements. The method includes: placing waste liquid produced by high-temperature gas-cooled reactor fuel elements in an evaporator for evaporation treatment to obtain steam and raffinate; The steam is condensed to obtain a condensate; the residual liquid is subjected to solid-liquid separation to obtain a filtrate and filter residue, and the filter residue is dried and then calcined to obtain a calcined product; and the condensate and calcined product are recovered to be used in the production of high-temperature gas-cooled reactor fuel elements. Since the method does not need to add other chemicals, it will not cause secondary pollution problems, and can recycle most of the useful substances in the waste liquid, realizing resource regeneration and utilization, and has significant environmental and economic benefits.

Description

technical field [0001] The disclosure belongs to the field of radioactive waste liquid treatment, and in particular relates to a treatment method and a treatment system for high temperature gas-cooled reactor fuel element production waste liquid. Background technique [0002] The characteristics and advantages of high temperature gas-cooled reactor (HTGR), such as inherent safety, multi-purpose and modular construction, make it competitive and attractive in the international nuclear power market. The basic unit of the HTGR fuel element is an all-ceramic coated particle dispersed in a graphite matrix, the center of which is the nuclear fuel uranium dioxide (UO 2 ) core, there are 2 to 4 layers of pyrolytic carbon and silicon carbide coatings with different thicknesses and densities on the outside of the core. The unique structure of coated particles prevents the leakage of radioactive substances and endangers the safety of the public and the environment even under accident c...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21F9/06G21F9/08G21F9/14
CPCG21F9/06G21F9/08G21F9/14
Inventor 李林艳徐建军程素伟陈晓彤刘兵唐亚平
Owner TSINGHUA UNIV